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Measurement ofk∞and Relative Reaction Rates in an H2O-Moderated UO2-PuO2Particulate Fueled Lattice

D.F. Newman

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Abstract

The neutron multiplication factor, k∞, and relative reaction rates have been measured at room temperature in the Physical Constants Testing Reactor (PCTR) for a water-moderated lattice fueled with Zircaloy-clad UO2-PuO2 fuel rods. The plutonium content in different sets of fuel rods ranged from 0.9 to 2.5 wt% PuO2 in UO2. These experiments provide neutronics data for uniform lattices of mixed-oxide fuels which contain plutonium oxide distributed throughout the uranium oxide as finite-sized particles. The PuO2 particle sizes in different sets of fuel rods ranged between 0 and 328 µm in diameter. Knowledge of the effect that plutonium particle size has on neutron multiplication is important for the economic utilization of plutonium. An experiment-theory correlation provides a basis for assessing the adequacy of calculational techniques.

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The neutron multiplication factor, k∞, and relative reaction rates have been measured at room temperature in the Physical Constants Testing Reactor (PCTR) for a water-moderated lattice fueled with Zircaloy-clad UO2-PuO2 fuel rods. The plutonium content in different sets of fuel rods ranged from 0.9 to 2.5 wt% PuO2 in UO2. These experiments provide neutronics data for uniform lattices of mixed-oxide fuels which contain plutonium oxide distributed throughout the uranium oxide as finite-sized particles. The PuO2 particle sizes in different sets of fuel rods ranged between 0 and 328 µm in diameter. Knowledge of the effect that plutonium particle size has on neutron multiplication is important for the economic utilization of plutonium. An experiment-theory correlation provides a basis for assessing the adequacy of calculational techniques.

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Available abstract

The neutron multiplication factor, k∞, and relative reaction rates have been measured at room temperature in the Physical Constants Testing Reactor (PCTR) for a water-moderated lattice fueled with Zircaloy-clad UO2-PuO2 fuel rods. The plutonium content in different sets of fuel rods ranged from 0.9 to 2.5 wt% PuO2 in UO2. These experiments provide neutronics data for uniform lattices of mixed-oxide fuels which contain plutonium oxide distributed throughout the uranium oxide as finite-sized particles. The PuO2 particle sizes in different sets of fuel rods ranged between 0 and 328 µm in diameter. Knowledge of the effect that plutonium particle size has on neutron multiplication is important for the economic utilization of plutonium. An experiment-theory correlation provides a basis for assessing the adequacy of calculational techniques.

Key concepts: Plutonium, Uranium oxide, Uranium dioxide, Rod, MOX fuel, Plutonium-240, Uranium, Americium

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